L-MT-07-031, Annual Radiological Environmental Operating Report

Annual Radiological Environmental Operating Report

ML071170143
Person / Time
Site:	Monticello
Issue date:	04/20/2007
From:	Conway J Nuclear Management Co
To:	Document Control Desk, NRC/NRR/ADRO
References
FOIA/PA-2010-0209, L-MT-07-031
Download: ML071170143 (59)

Text

SM NMC Committed to NuclearExcellence Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC April 20, 2007 L-MT-07-031 Technical Specification 5.6.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 2006 Annual Radioloqical Environmental Operatingq Report In accordance with the Monticello Nuclear Generating Plant Technical Specification 5.6.1, the Nuclear Management Company, LLC is submitting the Annual Radiological Environmental Operating Report for the year 2006.

This letter contains no new NRC commitments, nor does it modify any prior commitments.

n T. Conway ite Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce 2807 West County Road 75

• Monticello, Minnesota 55362-9637 Telephone: 763-295-5151

• Fax: 763-295-1454

ENCLOSURE1 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, JANUARY 1 TO DECEMBER 31, 2006 57 pages follow

N

.i,I Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

• Northbrook, IL 60062-2310 ph. (847) 564-0700 ° fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2006 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

EBr n1"Gro M.S.

La or ry anager

PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated' by Nuclear Management Company, LLC for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.

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TABLE OF CONTENTS No. Page Pre fa c e ............................................................................................................................... ii List of Ta b les ...................................................................................................................... iv List of Figures ............................................................................................................ v

1.0 INTRODUCTION

........................................................................................................ 1 2.0 SUM MARY .......................................................................................................................... 2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ................. 3 3.1 Program Design and Data Interpretation ......................................................... 3 3.2 Program Description ......................................................................................... 4 3.3 Program Execution ............................................................................................ 5 3.4 Laboratory Procedures .................................................................................... 6 3.5 Program Modifications ....................................................................................... 6 3.6 Land Use Census ............................................................................................. 6 4.0 RESULTS AND DISCUSSION ...................................................................................... 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents ................................ 7 4.2 Sum mary of Preoperational Data .................................................................... 7 4.3 Program Findings ............................................................................................. 8 5.0 FIGURES AND TABLES ............................................................................................... 12

6.0 REFERENCES

.................................................................................................................. 24 APPENDICES A Interlaboratory Com parison Program Results ................ I............................................. A-1 B Data Reporting Conventions ........................................................................................ B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area ....................................................... C-1 D Sam pling Location.Maps ............................................................................................. D-1 iii

LIST OF TABLES No. Title Pace 5.1 Sam ple Collection and Analysis Program ...................................................................... 13 5.2 Sam pling Locations .................................................................................................. 14 5.3 Missed Collections and Analyses .............................................................................. 16 5.4 Radiation Environmental Monitoring Program Sum m ary .......................................... 19 The following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results ........................................................... Al-1 A-2 Thermoluminescent dosimeters (TLDs) ........................................................................ A2-1 A-3 In-house Spiked Samples .............................................................................................. A3-1 A-4 In-house "Blank" Samples ............................................................................................. A4-1 A-5 In-house "Duplicate" Sam ples ................................................................................. A5-1 A-6 Department of Energy MAPEP comparison results ...................................................... A6-1 Attachment A: Acceptance criteria for spiked samples .............................................. A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ........................................................................ C-2 iv

LIST OF FIGURES No. Title 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations ...................................... 17 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location ......................................................................................... 18 Appendix D D-1 Sample collection and analysis program: TLD locations, In n er R in g ............................................................. .................................................................. D-2 D-2 Sample collection and analysis program: TLD locations, O u te r R in g ............................................................................................................................. D-3 D-3 Sample collection and analysis program: TLD locations, C o n tro ls ................................................................................................................................... D -4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk sam pling locations ...................................................................................................... D -5 D-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground water and Shoreline sampling locations ............................................... D-6 V

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2006.

This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.

Tabulation of the individual analyses made during the year are not included in this report.

These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2006a) available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 620 MWe. It is located on the Mississippi River in Wright County, Minnesota, and operated by Nuclear Management Company, LLC. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.

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2.0

SUMMARY

The Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating. Plant is described. Results for the year 2006 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.

No effect on the environment due to the operation of the Monticello Nuclear Generating Plant is indicated.

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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Desion and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant is to- assess the impact of the Plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLD's).

Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.

In interpreting the data, effects due to the Plant must be distinguished from those due to other sources.

A major interpretive aid in assessment of these effects is the design of the monitoring program at the Monticello Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive technique involves analyses for specific radionuclides present in environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-1 37, cerium-1 44, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation.

Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators. The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

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Program Design and Data Interpretation (continued)

Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the Plant's Monitoring Program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.

3.2 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision). Maps of sampling locations are included in Appendix D.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly.

Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-1 31. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (M-1), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).

Ambient gamma radiation is monitored at forty locations, using CaSO 4:Dy dosimeters with four sensitive areas at each location: fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.

Milk samples are collected monthly from three farms (two indicator and one control). There are currently only two milk producers within the indicator area. Milk is collected biweekly during the growing season (May - October), because the animals may be on pasture. Samples are analyzed for iodine-131 and gamma-emitting isotopes.

Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location and analyzed for iodine-131. Corn and potatoes are collected annually only if the field is irrigated by water in which liquid radioactive effluent has been discharged. Analysis is for gamma-emitting isotopes.

The terrestrial environment is also monitored by the quarterly collections of well water from eleven locations. Samples are analyzed for tritium and gamma-emitting isotopes.

River water is collected weekly at two locations, one upstream of the plant and one downstream.

Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

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Proaram Description (continued)

Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments. Shoreline sediment is also collected semi-annually from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.

3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:

(1) Air Particulates / Air Iodine:

No air particulate / air iodine samples were available from location M-1 for the weeks ending 06-14-06 through 07-12-06. There was no power to the substation.

(2) Milk:

Milk samples were not available from M-28 (Hoglund Farm) June 14th through October 25th, 2006. Dairy operations were temporarily discontinued. Collections were resumed on 11-22-06.

(3) Thermoluminescent Dosimeters:

TLDs for location M-08A and M-04S were missing for the second quarter, 2006. The TLDs were lost in the field.

(4) Surface Water:

Surface water could not be collected at location M-08 for the week of 12-20-06, due to freezing conditions. The monthly composite for December was made from three weekly collections.

Deviations from the program are summarized in Table 5.3.

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3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.

Levels of iodine-131 in cabbage and natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.

Tritium concentrations are determined by liquid scintillation.

Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.

Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.

3.5 Program Modifications Well Water, analysis for tritium and gamma-emitting isotopes.

Seven onsite monitoring wells (M-29 through M-35) were added to the program in the third quarter of 2006. (Tables 5.1, 5.2).

3.6 Land Use Census In accordance with the Offsite Dose Calculation Manual, sec. 07.01, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft 2 producing fresh leafy vegetables, in each.of the 16 meteorological sectors within a distance of 5 miles. The census shall also identify the locations of all milk animals and all 500 ft 2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May I and October 31. New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

The 2006 land use census was conducted between September 4.and September 11, 2006.

An increased D/Q value (> 20%) was calculated for the nearest garden in the NNW sector. A new garden was planted in the sector closer to the plant.

In summary, the highest D/Q locations for nearest resident, garden and nearest milk animal did not change from the 2005 census.

Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

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4.0 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.

All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents at nuclear facilities and no atmospheric nuclear tests conducted in the year 2006. The last reported test was made by the People's Republic of China on October 16, 1980.

4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross 2 2 beta measurements in fallout averaged 20,600 pCi/m in 1969 and 12,000 pCi/m in 1970. These levels are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 3 3 pCi/m . Present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-1 37 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L.

Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.

The aqueous environment was monitored by testing of river water, bottom sediments, fish, aquatic vegetation, and periphyton. Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L. Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-1 37 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.

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4.3 Proqram Findinqs Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.

Ambient Radiation (TLD's)

Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi.

distant from the Plant, at special interest areas and at four control locations. The means were similar for both inner and outer rings (16.5 and 15.6 mRem/91 days, respectively). The mean for special interest locations was 15.5 mRem/91 days and the mean for the control locations was 15.7 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1991 through 2005 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Ring Outer Rin Dose rate mRem/91 days) 1991 15.2 15.8 1992 15.1 15.1 1993 15.6 15.9 1994 14.6 14.0 1995 14.4 13.6 1996 14.0 13.5 1997 13.3 12.8 1998 15.0 14.4 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 15.9 14.8 2003 15.6 15.0 2004 16.0 15.4 2005 15.6 15.2 2006 16.5 15.6 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates, Inner vs. Outer Ring locations 8

Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at 3

indicator and control locations (0.024 and 0.025 pCi/m , respectively) and similar to levels observed from 1991 through 2005. The results are tabulated below.

Year Indicators Control 3

Concentration (pCi/m) 1991 0.024 0.024 1992 0.023 0.023 1993 0.024 0.023 1994 0.023 0.024 1995 0.024 0.025 1996 0.023 0.023 1997 0.023 0.023 1998 0.023 0.023 1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 2005 0.025 0.025 2006 0.024 .0.025 Average annual gross beta concentrations in airborne particulates.

A spring peak in beta activity had been observed almost annually for many years (Wilson et al.,

1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et aL, 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983.

The highest averages usually occur during the months of.January and December, and the first and fourth quarters, as seen in 1991 through 2005.

Two pieces of evidence indicate conclusively that seasonal elevated activities observed are not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations. Secondly, an identical pattern was observed at the Prairie Island Nuclear Generating Plant, about 100 miles distant from the Monticello Nuclear Generating Plant (XCEL Energy Corp., 2006b).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation 3(Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.074 pCi/rn for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

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Airborne Iodine Weekly levelsof airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m 3 in all samples.

Milk Iodine-1 31 activity measured below the detection limit of 0.5 pCi/L in all samples.

No gamma-emitting isotopes, excepting naturally-occurring potassium-40, were detected. This is consistent with the finding of the National Center for Radiological Health (1968) that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. Common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine.

In summary, the milk data for 2006 show no radiological effects of the plant operation.

River Water and Drinkina Water Tritium activity measured below the LLD of 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.1 pCi/L and was similar to average levels observed from 1991 through 2005. Gross beta averages are tabulated below.

Year Gross Beta (pCi/L) Year Gross Beta (pCi/L) 1991 2.9 1999 2.2 1992 2.1 2000 2.5 1993 2.6 2001 2.5 1994 2.0 2002 2.9 1995 2.3 2003 3.0 1996 2.1 2004 2.7 1997 2.3 2005 2.8 1998 2.4 2006 2.1 Average annual concentrations; Gross beta in drinking water.

Comparisons with data reported by the USEPA for Minneapolis drinking water samples collected from 1980 through 2005 indicate that concentrations of these nuclides are remaining fairly constant. Gamma-emitting isotopes were below detection limits in all surface water samples.

There was no indication of a plant effect.

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Well Water Tritium measured below the LLD level of 500 pCi/L in all samples. All gamma isotopic results were below detection limits. The data for 2006 were consistent with previous years results and no plant operational effects were indicated.

Crops Cabbage and broccoli were collected in September from three locations and analyzed for iodine-131. Levels of 1-131 measured below 0.023 pCi/g wet weight in both samples. Other gamma-emitting isotopes were below respective LLD levels. There was no indication of a plant effect.

There were no crops irrigated from the Mississippi River within 5 miles of the plant in 2006; therefore, no corn or potato samples were collected for analysis from irrigated fields.

Fish Fish samples were collected in May and October. Flesh was separated from the bones and analyzed by gamma spectroscopy. Naturally-occurring potassium-40 was found to be similar in upstream and downstream samples (2.98 and 3.48 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels. There was no indication of a plant effect.

Invertebrates Samples were collected in the second and fourth quarters of 2006, and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes were below detection limits. There was no indication of a plant effect.

Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in May and October and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in two of four downstream samples, averaging, 0.065 pCi/g dry weight, and 0.039 pCi/g dry weight in one of two control samples. Similar levels of activity and distribution have been observed since 1978, and are indicative of the influence of fallout deposition. The only gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40. There was no indication of a plant effect.

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5.0 FIGURES AND TABLES 12

Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type)a Frequencyb Frequencyc Ambient radiation 40 M-01A- M-14A C/Q Ambient gamma (TLDs) M-01B - M-16B M-01S - M-06S M-01C - M-04C Airborne Particulates 5 M-1(C), M-2, M-3, M-4, M-5 C/W GB, GS (QC of each location)

Airborne Iodine 5 M-1(C), M-2, M-3, M-4, M-5 C/W 1-131 Milk 3 M-10 (C), M-24, M-28 G/Md 1-131, GS Surface water 2 M-8(C), M-9 G/W GS(MC), H-3(QC)

Drinking water 1 M-14 G/W GB(MC), 1-131 (MC)

GS (MC), H-3 (QC)

Well water 4 M-10(C), M-11, M-12, M-27 G/Q H-3, GS M M-35 f Edible cultivated crops -

Come 1 M-19 G/A GS Leafy Vegetable 2 M-27, G/A 1-131 St. Cloud Farmer's Mkt. (C)

Potatoese 1 M-21 G/A GS Fish 2 M-8(C), M-9 G/SA GS (one species, edible portion)

Periphyton or invertebrates 2 M-8(C), M-9 G/SA GS Shoreline sediment 3 M-8(C), M-9, M-15 G/SA GS a Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.

Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows:

W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.

c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 =

iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.

d Milk is collected biweekly during the grazing season (May - October), if milch animals are on pasture.

e Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.

f M-29 through M-35, Onsite well locations added in the third quarter of 2006.

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Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Direction from Code Type' Collection Site Sample Typeb Reactor M-1 C Air Station M-1 AP, Al 11.0 mi @ 307°/NW M-2 Air Station M-2 AP, Al 0.8 mi @ 140°/SE M-3 Air Station M-3 AP, Al 0.6 mi @ 104°/ESE M-4 Air Station M-4 AP, Al 0.8 mi @ 146°/SSE M-5 Air Station M-5 AP, Al 2.6 mi @ 134°/SE M-8 C Upstream of Plant SW, SS, BO, F < 1000' upstream of Plant Intake M-9 Downstream of Plant SW, SS, BO, F < 1000' downstream of Plant Discharge M-1 0 C Campbell Farm M, WW 10.6 mi @ 357°/N M-1 1 City of Monticello WW 3.3 mi @ 127°/SE M-12 Plant Well #1 WW 0.26 mi @ 252°/SW M-14 City of Minneapolis DW 37.0 mi @ 132°/SE M-15 Montissippi Park SS 1.27 mi @ 114°/ESE M-1 9 River Irrigated Corn Fieldc M-21 River Irrigated Potato Fieldc M-24 Weinand Farm M 4.7 mi @ 1800/S M-27 Wise residence (Highest D/Q Garden) VE, WW 0.64 mi @ 207°/SSW

a. Available Producer VE > 10.0 mi.

M-28 Hoglund Farm M 3.8 mi @ 300°/WNW M-29 Warehouse #5 WW 276' @ 32°/NNE M-30 Receiving Warehouse WW 0.27 mi @ 156°/SSE M-31 Site Administration Building WW 424- @ 192°/SSW M-32 Shooting Range WW 0.33 mi @ 11 I°/ESE M-33 Monitoring Well #1 WW 593' @ 299°/WNW M-34 Monitoring Well #2 WW 749' @ 301 -/WNW M-35 Monitoring Well #3 WW 770' @ 304°/NW General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi @ 353°/N M-02A Sherburne Ave. So. TLD 0.79 mi @ 23°/NNE M-03A Sherburne Ave. So. TLD 1.29 mi @ 55°/NE M-04A Biology Station Road TLD 0.5 mi @ 86°/E M-05A Biology Station Road TLD 0.48 mi @ 118°/ESE M-06A Biology Station Road TLD 0.54 mi @ 135°/SE M-07A County Road 75 TLD 0.5 mi @ 155°/SSE M-08A County Road 75 TLD 0.48 mi @ 172°/S M-09A County Road 75 TLD 0.38 mi @ 209°/SSW M-10A County Road 75 TLD 0.38 mi @ 226°/SW M-11A County Road 75 TLD 0.4 mi @ 239°/WSW M-12A County Road 75 TLD 0.5 mi @ 262°/W M-13A North Boundary Road TLD 0.89 mi @ 324°/NW M-14A North Boundary Road TLD 0.78 mi @ 334°/NNW 14

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Direction from Code Type Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant M-01B Sherco #1 Air Station TLD 4.66 mi @ 02'/N M-02B County Road 11 TLD 4.4 mi @ 18°/NNE M-03B County Road 73 &81 TLD 4.3 mi @ 57°/NE M-04B County Road 73 (196th St.) TLD 4.2 mi @ 67°/ENE M-05B City of Big Lake TLD 4.3 mi @ 89°/E M-06B County Road 14 and 196th St. TLD 4.3 mi @ 117°/ESE M-07B Monte Industrial Drive TLD 4.3 mi @ 136 0/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi @ 162°/SSE M-09B Weinand Farm TLD 4.7 mi @ 178°/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 mi @ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi @ 228°/SW M-12B Lake Maria State Park TLD 4.2 mi @ 254°/WSW M-13B Bridgewater Station TLD 4.1 mi @ 270'/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi @ 289°/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi @ 309°/NW M-16B Sand Plain Research Farm TLD 4.4 mi @ 341'/NNW Special Interest Locations M-01S Osowski Fun Market TLD 0.66 mi @ 242°/WSW M-02S Krone Residence TLD 0.5 mi @ 224°/SW M-03S Big Oaks Park TLD 1.53 mi @ 102°/ESE M-04S Pinewood School TLD 2.3 mi @ 131°/SE M-05S Rivercrest Christian Academy TLD 3.0 mi @ 118°/ESE M-06S Monte Public Works TLD 2.6 mi @ 1341/SE M-01C C Kirchenbauer Farm TLD 11.5 mi @ 323°/NW M-02C C County Roads 4 and 15 TLD 11.2 mi @ 47°/NE M-03C C County Rd 19 and Jason Ave. TLD 11.6 mi @ 130°/SE M-04C C Maple Lake Water Tower TLD 10.3 mi @ 2260/ SW a "C" denotes control location. All other locations are indicators.

b Sample Codes:

AP Airborne particulates F Fish Al Airborne Iodine M Milk BS Bottom (river) sediments RW River Water BO Bottom organisms SS Shoreline Sediments DW Drinking Water VE Vegetation / vegetables WW Well Water CCollected only ifthe plant discharges radioactive effluent into the river, then only from river irrigated fields.

15

Table 5.3. Missed collections and analyses at the Monticello Nuclear Generating Plant.

All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, M-01 6/14/2006 No power to substation. None required.

1-131 through 7/12/2006 Ml Gamma, M-28 6/14/2006 Hoglund Dairy temporarily out Hoglund will inform the MNGP 1-131 through of business for the summer. upon resumption of operation.

10/25/2006 Operation resumed 11/22/06.

TLD Ambient M-04S 2nd. Qtr. TLD lost in field. None required.

Gamma 2006 TLD Ambient M-08A 2nd. Qtr. TLD lost in field. None required.

Gamma 2006 SW Gamma M-08 12/20/2006 Shoreline frozen. None required.

H-3 16

Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

20 19 18 17 16 15 14 E 13 12 11 10 M ItJ U') (0 r- Co 0) 0 -o IT L0~U) (

0) 0)

M ) 0) 0) 0 0 0 0 0, 0

) ) 0 0) 0 0) 0 0 0 0 0 0 0 0 0

-2 ONJ (N NN (N4 (NJ. (N 17

Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.

Indicators (M-2, 3, 4, 5) 0.035 0.033 0.031 0.029 0.027 0.025 C 0.023 76-----._ _-__ ____

" 0.021 0.019 0.017 0.015 OO I 0) M* 0) a) a)Ob I)ý2 0)

T T T 0 OO 0: 0 0

(

0 C) 0 0"C14 C Control (M-1) 0.035 0.033 _

0.031 0.023 0.025 _' _ I

. 0.023 0 .021 -L 0.019 0.017 0.015 04 0) 0 O O) 0 0 0) CD 0 04 M 0 0 0 0 0) 0) 0) 0) 0) 0) 0) 0) 0 0 0 0 0 0 0 04 NJ ( N (N N 04 (N N 18

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2006

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses" Rangec Locationd Rangec Rangec Resultse TLD (Inner Ring, Gamma 55 3.0 16.5 (55/55) M-11A 18.6(4/4) (See Control 0 General Area at (13.4-19.9) 0.4 mi @ 239°/WSW (16.2-19.9) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 64 3.0 15.6 (64/64) M-09B, Weinand Farm 17.0 (4/4) (See Control 0 4-5 mi. distant) (12.2-18.7) 4.7 mi @ 178°/S (16.0-18.7) below.)

mRem/91 days)

TLD (Special Gamma 23 3.0 15.5 (23/23) M-06S, Mont. Pub. Wks. 17.3 (4/4) (See Control 0 Interest Areas) (12.3-18.5) 2.6 mi @ 134°/SE (16.3-18.0) below.)

mRem/91 days)

TLD (Control) Gamma 16 3.0 None M-03C, County Rd.19 & 16.7 (4/4) 15.7 (16/16) 0 mRem/91 days) Jason, 11.6 mi. @ 130°/SE (14.9-17.7) (13.7-17.7)

Airborne GB 255 0.005 0.024 (208/208) M-1 (C) 0.025 (47 /47) 0.025 (47/47) 0 Particulates (0.006-0.055) 11.0 mi @ 307°/NW (0.007-0.053) (0.007-0.053)

(pCi/m 3 )

GS 20 Be-7 0.015 0.072 (16/16) M-1 (C) 0.081 (4/4) 0.081 (4/4) 0 (0.043-0.109) 11.0 mi @ 307°/NW (0.062-0.098) (0.062-0.098)

Mn-54 0.0009 < LLD < LLD 0 Co-58 0.0010 < LLD < LLD 0 Co-60 0.0010 < LLD < LLD 0 Zn-65 0.0017 < LLD < LLD 0 Zr-Nb-95 0.0019 < LLD < LLD 0 Ru-1 03 0.0013 < LLD < LLD 0 Ru-106 0.0080 < LLD < LLD 0 Cs-134 0.0009 < LLD - < LLD 0 Cs-137 0.0007 < LLD - < LLD 0 Ba-La-140 0.0042 < LLD - < LLD 0 Ce-141 0.0040 < LLD - <LLD 0 Ce-144 0.0056 < LLD - < LLD 0 Airborne Iodine 1-131 255 0.03 < LLD - < LLD 0 (pCi/m 3 )

19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2006

( County, State Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine Analysesa Range' Locationd Rangec Rangec Resultse (Units)

Milk (pCi/L) 1-131 49 0.5 < LLD < LLD 0 GS 49 K-40 200 1327 (29/29) M-10 (C), Campbell 1361 (20/20) 1361 (20/20) 0 (1093-1428) 10.6 mi @ 357°/N (1205-1520) (1205-1520)

Cs-134 5 < LLD < LLD 0 Cs-137 5 < LLD < LLD 0 Ba-La-140 5 < LLD < LLD 0 River Water H-3 8 500 < LLD - < LLD 0 (pCi/L)

GS 24 Mn-54 10 < LLD - -< LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - -< LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - -< LLD 0 Cs-134 10 < LLD - -< LLD 0 Cs-137 10 < LLD - -< LLD 0 Ba-La-140 15 < LLD - -< LLD 0 Ce-144 50 < LLD - -< LLD 0 20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2006

( County, State Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa - Rangec Locationd Rangec Rangec Resultse Drinking Water GB 12 1.0 2.1 (12112) M-14, Minneapolis 2.1 (12/12) None 0 (pCi/L) (1.1-3.1) 37.0 mi. @ 132' /SE (1.1-3.1) 1-131 12 1.0 < LLD None 0 H-3 4 500 < LLD None 0 GS 12 Mn-54 10 < LLD None 0 Fe-59 30 < LLD None 0 Co-58 10 < LLD - None 0 Co-60 10 < LLD - None 0 Zn-65 30 < LLD - None 0 Zr-Nb-95 15 < LLD - - None 0 Cs-134 10 < LLD - - None 0 Cs-137 10 < LLD - - None 0 Ba-La-140 15 < LLD - - None 0 Ce-144 55 < LLD - - None 0 Well Water H-3 30 500 < LLD - - < LLD 0 (pCi/L)

GS 30 Mn-54 10 < LLD < LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 10 < LLD - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0

-Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - -< LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 56 < LLD - -< LLD 0 Crops - Cabbage GS 2 (pCi/gwet) 1-131 0.023 < LLD < LLD 0 Cs-134 0.014 < LLD < LLD 0 Cs-137 0.013 < LLD < LLD 0 21

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2006

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Fish GS 4 (pCi/g wet) K-40 0.10 3.48 (2/2) M-09, Downstream 3.48 (2/2) 2.98 (2/2) 0 (3.13-3.83) < 1000' of discharge (3.13-3.83) (2.47-3.48)

Mn-54 0.021 < LLD < LLD 0 Fe-59 0.043 < LLD < LLD 0 Co-58 0.019 < LLD < LLD 0 Co-60 0.029 < LLD < LLD 0 Zn-65 0.053 < LLD < LLD 0 Zr-Nb-95 0.028 < LLD < LLD 0 Cs-134 0.018 < LLD < LLD 0 Cs-137 0.022 < LLD < LLD 0 Ba-La-140 0.051 < LLD < LLD 0 Ce-144 0.18 < LLD < LLD 0 Invertebrates GS 4 (pCi/g wet) Be-7 0.66 < LLD < LLD 0 K-40 1.33 < LLD M-09, Downstream 1.38 (1/2) < LLD 0

< 1000' of discharge Mn-54 0.049 < LLD < LLD 0 Fe-59 0.17 < LLD < LLD 0 Co-58 0.061 < LLD < LLD 0 Co-60 0.054 < LLD < LLD 0 Zn-65 0.11 < LLD - < LLD 0 Zr-Nb-95 0.13 < LLD - < LLD 0 Ru-103 0.11 < LLD - < LLD 0 Ru-106 0.47 < LLD - < LLD 0 Cs-134 0.055 < LLD - < LLD 0 Cs-1 37 0.052 < LLD - < LLD 0 Ba-La-140 0.29 < LLD - < LLD 0 Ce-144 0.31 < LLD - < LLD 0 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2006

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Range' Resultse Shoreline GS 6 Sediments Be-7 0.29 0.32 (1/4) M-15, Montissippi Park 0,32 (1/2) < LLD 0 (pCi/g dry) 1.27 mi @ 114°/ESE K-40 0.10 10.86 (4/4) M-15, Montissippi Park 11.52 (2/2) 10.50 (2/2) 0 (9.45-11.54) 1.27 mi @ 114°/ESE (11,49-11.54) (10.46-10.53)

Mn-54 0.027 < LLD < LLD 0 Fe-59 0.089 < LLD < LLD 0 Co-58 0.028 < LLD < LLD 0 Co-60 0.022 < LLD < LLD 0 Zn-65 0.057 < LLD < LLD 0 Nb-95 0.034 < LLD < LLD 0 Zr-95 0.070 < LLD < LLD 0 Ru-103 0.029 < LLD < LLD 0 Ru-106 0.18 < LLD < LLD 0 Cs-134 0.031 < LLD < LLD 0 Cs-137 0.026 0.065 (2/4) M-09, Downstream 0.070 (1/2) 0.039 (1/2) 0 (0.060-0.070) < 1000' of discharge Ba-La-140 0.099 < LLD < LLD 0 Ce-144 0.15 < LLD < LLD 0 a GB gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

o Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

d Locations are specified: (1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.

e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.

23

6.0 REFERENCES

CITED Arnold, J. R. and H. A. AI-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.

Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, 276.

Environmental, Inc., Midwest Laboratory.

2001a through 2007a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2006.

2001b through 2007b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2006.

2003. Quality Assurance Program Manual, Rev. 1, 01 October 2003.

2005. Quality Control Procedures Manual, Rev. 0, 17 September 2005.

2003. Quality Control Program, Rev. 1, 21 August 2003.

Gold, S., H.W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Illinois, 369-382.

Hazleton Environmental Sciences Corporation.

1979a through 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

1979b through 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel, 1986. "Chernobyl," Chemtech, October 1986, pp. 596-605.

National Center for Radiological Health, 1968. Radiological Helath and Data Reports, Vol. 9, Number 12, 730-746.

Northern States Power Company.

1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.

Northern States Power Company.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.

Nuclear Regulatory Commission, January 1, to December 31, 1977 through 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1984 through 2000. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental -Services, Midwest Laboratory). Northbrook, Illinois 24

6.0 REFERENCES

CITED (continued)

Teledyne Brown Engineering Environmental Services, Midwest Laboratory.

1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.

U.S. Environmental Protection Agency.

1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).

1984. Eastem Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).

2007. RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981- 2005.

Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.

XCEL Energy Corporation.

2007. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2006. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 25

- , Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700

• fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2006 through December, 2006

Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Attachment A lists acceptance criteria for "spiked" samples.

Out-of-limit results are explained directly below the result.

Al

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value Strontium-889b 5 to 50 pCi/liter or kg 5.0 pCi/liter

> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium-40 > 0.1 g/liter or kg 5% of known value Gross alpha < 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value Gross beta -<100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium -4,000 pCi/liter lo = (pCi/liter) =

0 0 933 169.85 x (known)

> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium > 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, < 55 pCi/liter 6.0 pCi/liter Iodine-129b > 55 pCi/liter 10% of known value Uranium-238, < 35 pCi/liter 6.0 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Othersb 20% of known value 0 From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 078 01/16/06 Sr-89 49.9 +/- 3.5 50.2 41.5 - 58.9 Pass STW-1078 01/16/06 Sr-90 31.5 +/- 1.5 30.7 22.0 -39.4 Pass STW-1079 01/16/06 Ba-133 86.5 +/- 4.1 95.0 78.6 -111.0 Pass STW-1 079 01/16/06 Co-60 96.3 +/- 4.1 95.3 86.6 - 104.0 Pass STW-1079 01/16/06 Cs-134 22.6 +/- 3.0 23.1 14.4 -31.8 Pass STW-1079 01/16/06 Cs-137 109.0 +/- 5.9 111.0 101.0 - 121.0 Pass STW-1079 01/16/06 Zn-65 198.0 +/- 11.2 192.0 159.0 -225.0 Pass STW-1080 01/16/06 Gr. Alpha 10.8 +/- 1.4 9.6 1.0 -18.3 Pass STW-1080 01/16/06 Gr. Beta 56.9 +/- 1.9 61.9 44.6 -79.2 Pass STW-1 081 01/16/06 Ra-226 4.3 +/- 0.4 4.6 3.4 -5.8 Pass STW-1081 01/16/06 Ra-228 7.1 +/- 1.8 6.6 3.7 -9.5 Pass STW-1 081 01/16/06 Uranium 20.7 +/- 0.5 22.1 16.9 -27.3 Pass STW-1088 04/10/06 Sr-89 29.0 +/- 1.8 32.4, 23.7 -41.1 Pass STW-1 088 04/10/06 Sr-90 8.7 +/- 1.0 9.0 0.3 - 17.7 Pass STW-1089 04/10/06 Ba-133 10.3 +/- 0.4 10.0 1.3 - 18.7 Pass STW-1089 04/10/06 Co-60 114.0 +/- 2.8 113.0 103.0 - 123.0 Pass STW-1089 04/10/06 Cs-134 41.9 +/- 1.4 43.4 34.7 -52.1 Pass STW-1089 04/10/06 Cs-137 208.0 +/- 1.1 214.0 195.0 -233.0 Pass STW-1089 04/10/06 Zn-65 154.0 +/- 0.8 152.0 126.0 - 178.0 Pass STW-1 090 04/10/06 Gr. Alpha 13.4 +/- 1.1 21.3 12.1 -30.5 Pass STW-1090 04/10/06 Gr. Beta 27.7 +/- 2.1 23.0 14.3 -31.7 Pass STW-1091 04/10/06 1-131 22.0 +/- 0.3 19.1 13.9 -24.3 Pass STW-1092 04/10/06 H-3 7960.0 +/- 57.0 8130.0 6720.0 - 9540.0 Pass STW-1 092 04/10/06 Ra-226 2.9 +/- 0.4 3.0 2.2 -3.8 Pass STW-1092 04/10/06 Ra-228 20.9 +/- 1.2 19.1 10.8 -27.4 Pass STW-1092 04/10/06 Uranium 68.6 +/- 3.4 69.1 57.1 -81.1 Pass STW-1094 07/10/06 Sr-89 15.9 +/- 0.7 19.7 11.0 -28.4 Pass STW-1 094 07/10/06 Sr-90 24.3 +/- 0.4 25.9 17.2 -34.6 Pass STW-1 095 07/10/06 Ba-1 33 94.9 +/- 8.9 88.1 72.9 - 103.0 Pass STW-1 095 07/10/06 Co-60 104.0 +/- 1.8 99.7 91.0 -108.0 Pass STW-1095 07/10/06 Cs-134 48.7 +/- 1.3 54.1 45.4 -62.8 Pass STW-1 095 07/10/06 Cs-137 236.0 +/- 3.0 238.0 217.0 -259.0 Pass STW-1095 07/10/06 Zn-65 126.0 +/- 8.0 121.0 100.0 - 142.0 Pass STW-1 096 07/10/06 Gr. Alpha 10.9 +/- 1.0 10.0 1.3 - 18.6 Pass STW-1 096 07/10/06 Gr. Beta 9.7 +/- 0.4 8.9 0.2 - 17.5 Pass STW-1 097 07/10/06 Ra-226 11.0 +/- 0.5 10.7 7.9 -13.5 Pass STW-1097 07/10/06 Ra-228 12.2 +/- 0.8 10.7 6.1 - 15.3 Pass STW-1097 07/10/06 Uranium 43.4 +/- 0.1 40.3 33.3 -47.3 Pass A1-1

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1104 10/06/06 Sr-89 38.4 +/- 1.3 39.9 31.2 -45.7 Pass STW-1104 10/06/06 Sr-90 15.5 +/- 0.5 16.0 7.3 - 24.7 Pass STW-1105 10/06/06 Ba-133 64.9 +/- 2.8 70.2 58.1 - 82.3 Pass STW-1105 10/06/06 Co-60 61.6 +/- 1.0 62.3 53.6 -71.0 Pass STW-1105 10/06/06 Cs-134 29.0 +/- 0.9 29.9 21.2 - 38.6 Pass STW-1105 10/06/06 Cs-1 37 77.8 +/- 2.4 78.2 69.5 - 86.9 Pass STW-1 105 10/06/06 Zn-65 293.0 +/- 2.4 277.0 229.0 - 325.0 Pass STW-1 106 .10/06/06 Gr. Alpha 23.9 +/- 2.5 28.7 16.3 -41.1 Pass STW-1106 10/06/06 Gr. Beta 23.7 +/- 1.4 20.9 12.2 - 29.6 Pass STW-1107 10/06/06 1-131 28.4 +/- 1.2 22.1 16.9 - 27.3 Fail STW-1 108 10/06/06 Ra-226 14.5 +/- 0.5 14.4 10.7 - 18.1 Pass STW-1 108 10/06/06 Ra-228 6.6 +/- 0.4 5.9 3.3 - 8.4 .Pass STW-1108 10/06/06 Uranium 2.9 +/-0.1 3.2 0.0 - 8.4 Pass STW-1109 10/06/06 H-3 3000.0 +/- 142.0 3050.0 2430.0 - 3670.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the-mean +/- standard deviation for three determinations.

Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.

The reported result was an average of three analyses, results ranged from 25.36 to 29.23 pCi/L.

A fourth analysis was performed, result of analysis, 24.89 pCi/L.

Al -2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).

mR Lab Code Date Known Lab Result Control Description Value + 2 sigma Limits Acceptance Environmental, Inc.

2006-1 6/5/2006 30 cm 54.81 70.73 +/- 0.69 38.37 - 71.25 Pass 2006-1 6/5/2006 60 cm 13.70 16.71 +/- 1.89 9.59 - 17.81 Pass 2006-1 6/5/2006 60 cm 13.70 16.69 +/- 0.94 9.59 - 17.81 Pass 2006-1 6/5/2006 90 cm 6.09 6.57 +/- 0.82 4.26 - 7.92 Pass 2006-1 6/5/2006 120 cm 3.43 3.65 +/- 0.22 2.40 - 4.46 Pass 2006-1 6/5/2006 120 cm 3.43 3.09 +/- 0.33 2.40 - 4.46 Pass 2006-1 6/5/2006 150 cm 2.19 2.35 +/- 0.38 1.53 -2.85 Pass 2006-1 6/5/2006 150 cm 2.19 1.98 +/- 0.10 1.53 - 2.85 Pass 2006-1 6/5/2006 180 cm 1.52 1.56 +/- 0.26 1.06 -1.98 Pass Environmental, Inc.

2006-2 11/6/2006 30 cm. 55.61 60.79 +/- 1.32 38.93 - 72.29 Pass 2006-2 11/6/2006 40 cm. 31.28 35.93 +/- 3.70 21.90 - 40.66 Pass 2006-2 11/6/2006 50 cm. 20.02 21.55 +/- 1.20 14.01 -26.03 Pass 2006-2 11/6/2006 60 cm. 13.90 14.90 +/- 1.42 9.73 - 18.07 Pass 2006-2 11/6/2006 75 cm. 8.90 8.03 +/- 0.51 6.23 -11.57 Pass 2006-2 11/6/2006 90 cm. 6.18 6.88 +/- 0.68 4.33 - 8.03 Pass 2006-2 11/6/2006 120 cm. 3.48 2.90 +/- 0.20 2.44 -4.52 Pass 2006-2 11/6/2006 150 cm. 2.22 1.99 +/- 0.07 1.55 - 2.89 Pass 2006-2 11/6/2006 180 cm. 1.54 1.79 +/- 0.94 1.08 -2.00 Pass A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 C Activity Limits d Acceptance SPW-301 1/20/2006 Fe-55 2700.10 +/- 70.00 2502.50 2002.00 -3003.00 Pass SPAP-1224 3/7/2006 Cs-134 37.13 +/- 3.70 39.52 29.52 -49.52 Pass SPAP-1224 3/7/2006 Cs-137 118.25 +/- 8.97 119.30 107.37 - 131.23 Pass SPAP-1224 3/7/2006 Gr. Beta 520.32 +/- 7.42 455.00 364.00 - 637.00 Pass SPW-1228 3/7/2006 H-3 70891.00 +/- 719.00 75394.00 60315.20 - 90472.80 Pass SPW-1230 3/7/2006 Cs-1 34 38.58 +/- 2.10 39.51 29.51 -49.51 Pass SPW-1230 3/7/2006 Cs-137 59.44 +/- 4.51 59.65 49.65 - 69.65 Pass SPMI-1232 3/7/2006 Cs-134 41.20 +/- 1.33 39.51 29.51 - 49.51 Pass SPMI-1232 3/7/2006 Cs-137 57.82 +/- 3.96 59.65 49.65 - 69.65 Pass W-30906 3/9/2006 Gr. Alpha 24.24 +/- 0.47 20.08 10.04 -30.12 Pass W-30906 3/9/2006 Gr. Beta 63.79 +/- 0.48 65.73 55.73 - 75.73 Pass SPW-2750 4/27/2006 Ni-63 116.00 +/- 2.49 100.00 60.00 - 140.00 Pass SPW-2869 5/1/2006 Fe-55 19473.00 +/- 188.00 23332.00 18665.60 - 27998.40 Pass SPAP-2871 5/1/2006 Cs-1 34 33.97 +/- 1.10 37.50 27.50 -47.50 Pass SPAP-2871 5/1/2006 Cs-1 37 114.44 +/- 2.81 118.90 107.01 -130.79 Pass SPW-2875 5/1/2006 - H-3 71057.00 +/- 730.20 75394.00 60315.20 - 90472.80 Pass STSO-3155 5/1/2006 Co-60 7950.80 +/- 67.29 7750.00 6975.00 - 8525.00 Pass STSO-3155 5/1/2006 Cs-1 34 12.49 +/- 0.13 11.59 1.59 -21.59 Pass STSO-3155 5/1/2006 Cs-1 37 14.10 +/- 0.12 11.63 1.63 -21.63 Pass SPAP-2873 5/2/2006 Gr. Beta 1724.80 +/- 4.51 1744.00 1395.20 -2441.60 Pass SPF-3183 5/10/2006 Cs-1 37 2.47 +/- 0.03 2.38 1.43 - 3.33 Pass SPF-3183 5/10/2006 Cs-1 34 0.73 +/- 0.01 0.74 0.44 -1.04 Pass SPW-3460 5/26/2006 C-1 4 4009.60 +/- 14.43 4741.00 2844.60 - 6637.40 Pass W-60606 6/6/2006 Gr. Alpha 21.94 +/- 0.46 20.08 10.04 - 30.12 Pass W-60606 6/6/2006 Gr. Beta 58.17 +/- 0.49 65.73 55.73 - 75.73 Pass SPW-3988 6/16/2006 Cs-134 35.56 +/- 1.40 36.00 26.00 -46.00 Pass SPW-3988 6/16/2006 Cs-137 60.23 +/- 2.72 59.27 49.27 - 69.27 Pass SPW-3988 6/16/2006 1-131(G) 94.01 +/- 4.38 99.30 89.30 - 109.30 Pass SPW-3988 6/16/2006 Sr-89 52.40 +/- 4.23 58.16 46.53 - 69.79 Pass SPW-3988 6/16/2006 Sr-90 45.35 +/- 1.95 41.21 32.97 - 49.45 Pass SPMI-3990 6/16/2006 Cs-134 35.52 +/- 5.05 36.00 26.00 -46.00 Pass SPMI-3990 6/16/2006 Cs-1 37 56.78 +/- 3.86 59.27 49.27 - 69.27 Pass SPMI-3990 6/16/2006 1-131(G) 95.04 +/- 5.05 99.30 89.30 - 109.30 Pass SPMI-3991 6/16/2006 1-131 96.55 +/- 0.87 99.30 79.44 -119.16 Pass SPW-4356 7/5/2006 1-131 80.88 +/- 1.09 77.23 61.78 -92.68 Pass W-90506 9/5/2006 Gr. Alpha 23.11 +/- 0.45 20.08 10.04 -30.12 Pass W-90506 9/5/2006 Gr. Beta 65.01 +/- 0.51 65.73 55.73 - 75.73 Pass SPAP-6950 9/30/2006 Cs-1 34 28.93 +/- 1.56 32.65 22.65 - 42.65 Pass SPAP-6950 9/30/2006 Cs-1 37 116.62 +/- 2.97 117.75 105.98 - 129.53 Pass SPAP-6952 9/30/2006 Gr. Beta 52.96 _+0.14 53.50 42.80 - 74.90 Pass A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)

Lab Code Date Analysis Laboratory results Known Control 2s, n=1b Activity Limitsc Acceptance SPW-6954 9/30/2006 Cs-1 34 63.29 +/- 8.24 65.30 55.30 - 75.30 Pass SPW-6954 9/30/2006 Cs-1 37 60.41 +/- 7.53 58.87 48.87 - 68.87 Pass SPMI-6956 9/30/2006 Cs-1 34 69.26 +/- 4.85 65.31 55.31 - 75.31 Pass SPMI-6956 9/30/2006 Cs-1 37 61.35 +/- 7.62 58.87 48.87 - 68.87 Pass W-1 20106 12/1/2006 Gr. Alpha 22.40 +/- 1.03 20.08 10.04 -30.12 Pass W-120106 12/1/2006 Gr. Beta 63.70 +/- 1.14 65.73 55.73 - 75.73 Pass SPAP-9476 12/29/2006 Gr. Beta 57.51 +/- 0.14 53.16 42.53 - 74.42 Pass SPAP-9478 12/29/2006 Cs-134 26.84 +/- 1.23 30.06 20.06 -40.06 Pass SPAP-9478 12/29/2006 Cs-137 110.54 +/- 3.12 117.10 105.39 - 128.81 Pass SPW-9480 12/29/2006 H-3 68972.20 +/- 748.00 72051.60 57641.28 -86461.92 Pass SPW-9483 12/29/2006 Tc-99 29.43 +/- 0.84 32.98 20.98 -44.98 Pass SPW-9488 12/29/2006 Cs-1 34 61.35 +/- 1.65 60.10 50.10 -70.10 Pass SPW-9488 12/29/2006 Cs-137 60.30 +/- 2.76 56.80 46.80 - 66.80 Pass SPMI-9490 12/29/2006 Cs-1 34 58.99 +/- 5.43 60.10 50.10 -70.10 Pass SPMI-9490 12/29/2006 Cs-1 37 54.16 +/- 7.85 56.80 46.80 - 66.80 Pass SPF-9492 12/29/2006 Cs-134 0.64 +/- 0.01 0.60 0.36 - 0.84 Pass SPF-9492 12/29/2006 Cs-137 2.61 +/- 0.03 2.34 1.40 -3.28 Pass 3

a Liquid sample results are reported ini pCi/Liter, air filters( pCi/filter), charcoal (pCi/m ), and solid samples (pCi/g).

b Laboratory codes as follows: W (water), MI (milk), AP (air filter), SO (soil), VE (vegetation),

CH (charcoal canister), F (fish).

c Results are based on single determinations.

d Control limits are based on Attachment A, Page A2 of this report.

NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

A3-2

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 a)

I SPW-302 water 1/20/2006 Fe-55 21.21 -1.82 +/- 12.75 1000 SPAP-1 225 Air Filter 3/7/2006 Gr. Beta 1.16 -0.512 +/- 51.20 3.2 SPW-1231 water 3/7/2006 Cs-134 2.71 10 SPW-1231 water 3/7/2006 Cs-137 2.05 10 W-30906 water 3/9/2006 Gr. Alpha 0.037 0,005 +/- 0.026 1 W-30906 water 3/9/2006 Gr. Beta 0.076 -0.016 +/- 0.052 3.2 SPW-2751 water 4/27/2006 Ni-63 1.48 0.37 +/- 0.91 20 SPW-2868 water 5/1/2006 Fe-55 18.07 4.33 +/- 11.27 1000 SPW-2874 water 5/1/2006 H-3 166.00 -8.3 +/- 86.9 200 SPAP-2872 Air Filter 5/2/2006 Gr. Beta 1.18 -3.65 +/- 0.64 3.2 SPF-3154 Fish 5/10/2006 Cs-134 16.4 100 SPF-3154 Fish 5/10/2006 Cs-137 13.7 100 SPW-3461 water 5/26/2006 C-14 10.20 -7.9 +/- 5.20 200 W-60606 water 6/6/2006 Gr. Alpha 0.05 0.013 +/- 0.037 1 W-60606 water 6/6/2006 Gr. Beta 0.16 -0.044 +/- 0.11 3.2 SPW-3989 water 6/16/2006 Cs-1 34 3.00 10 SPW-3989 water 6/16/2006 Cs-1 37 3.65 10 SPW-3989 water 6/16/2006 1-131 0.21 0.045 +/- 0.14 0.5 SPW-3989 water 6/16/2006 1-131(G) 8.34 20 SPW-3989 water 6/16/2006 Sr-89 0.54 0.005 +/- 0.45 5 SPW-3989 water 6/16/2006 Sr-90 0.58 -0.079 +/- 0.26 1 SPMI-3991 Milk 6/16/2006 Cs-134 4.42 10 SPMI-3991 Milk 6/16/2006 Cs-137 3.88 10 SPMI-3991 Milk 6/16/2006 1-131 0.28 -0.22 +/- 0.19 0.5 SPMI-3991 Milk 6/16/2006 1-131(G) 3.76 20 SPMI-3991 Milk 6/16/2006 Sr-89 0.61 -0.25 +/- 0.76 5 SPMI-3991 d Milk 6/16/2006 Sr-90 0.52 0.88 +/- 0.34 1 W-90506 water 9/5/2006 Gr. Alpha 0.06 0.00 +/- 0.04 1 W-90506 water 9/5/2006 Gr. Beta 0.16 0.05 +/- 0.11 3.2 SPMI-6383 Milk 9/14/2006 Sr-89 0.97 -0.18 +/- 0.92 5 SPMI-6383 d Milk 9/14/2006 Sr-90 0.57 0.65 +/- 0.33 1 SPAP-6949 Air Filter 9/30/2006 Cs-1 34 0.89 100 SPAP-6949 Air Filter 9/30/2006 Cs-1 37 0.91 100 SPAP-6951 Air Filter 9/30/2006 Gr. Beta 1.12 -0.54 +/- 0.64 3.2 SPW-6953 water 9/30/2006 Cs-134 3.91 10 SPW-6953 water 9/30/2006 Cs-137 5.61 10 SPW-6953 water 9/30/2006 Sr-89 0.79 -0.14 +/- 0.64 5 SPW-6953 water 9/30/2006 Sr-90 0.60 0.11 +/- 0.29 1 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)2 Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 a)

SPMI-6955 Milk 9/30/2006 Cs-1 34 2.86 10 SPMI-6955 Milk 9/30/2006 Cs-1 37 2.39 10 SPMI-6955 Milk 9/30/2006 1-131(G) 9.98 0.5 W-120106 water 12/1/2006 Gr. Alpha 0.11 0.066 +/- 0.072 1 W-120106 water 12/1/2006 Gr. Beta 0.30 0.093 +/- 0.16 3.2 SPAP-9477 Air Filter 12/29/2006 Gr. Beta 1.13 -0.37 +/- 0.66 3.2 SPAP-9479 Air Filter 12/29/2006 Cs-1 37 0.87 100 SPW-9481 water 12/29/2006 H-3 146.2 63.2 +/- 80.1 200 SPW-9483 water 12/29/2006 Tc-99 0.95 -1.20 +/- 0.56 10 SPW-9489 water 12/29/2006 Cs-1 34 2.30 10 SPMI-9491 Milk 12/29/2006 Cs-1 34 3.10 10 SPMI-9491 Milk 12/29/2006 Cs-1 37 2.90 10 SPMF-9491 Milk 12/29/2006 1-131(G) 8.00 20 SPF-9493 Fish 12/29/2006 Cs-1 34 7.6 100 SPF-9493 Fish 12/29/2006 Cs-1 37 7.9 100 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b 1-131(G); iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported d Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)2 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7466, 7467 1/3/2006 Be-7 0.053 +/- 0.015 0.057 +/- 0.011 0.055 +/- 0.009 Pass AP-7513, 7514 1/3/2006 Be-7 0.033 +/- 0.008 0.036 +/- 0.008 0.035 +/- 0.006 Pass AP-7555, 7556 1/3/2006 Be-7 0.053 +/- 0.007 0.054 +/- 0.008 0.053 +/- 0.005 Pass MI-154, 155 1/10/2006 K-40 1254.20 +/- 87.75 1369.60 +/- 102.80 1311.90 +/- 67.58 Pass MI-217, 218 1/11/2006 K-40 1258.00 +/- 118.00 1313.00 +/- 98.00 1285.50 +/- 76.69 Pass MI-217, 218 1/11/2006 Sr-90 1.27 +/- 0.37 0.92 +/- 0.33 1.10 +/- 0.25 Pass MI-287, 288 1/17/2006 K-40 1383.10 +/- 110.90 1457.80 +/- 119.10 1420.45 +/- 81.37 Pass MI-287, 288 1/17/2006 Sr-90 0.74 +/- 0.38 0.94 +/- 0.37 0.84 +/- 0.27 Pass WW-314, 315 1/19/2006 Gr. Beta 9.21 +/- 1.72 11.52 +/- 1.93 10.37 +/- 1.29 Pass WW-314, 315 1/19/2006 H-3 168.64 +/- 94.94 210.12 +/- 96.51 189.38 +/- 67.69 Pass SWT-577, 578 1/31/2006 Gr. Beta 3.06 +/- 0.66 3.68 +/- 0.64 3.37 +/- 0.46 Pass SWU-598, 599 1/31/2006 Gr. Beta 2.03 +/- 0.39 1.97 +/- 0.40 2.00 +/- 0.28 Pass SWU-598, 599 1/31/2006 H-3 260.10 +/- 98.20 134.10 +/- 93.50 197.10 +/- 67.80 Pass F-3311, 3312 b 2/9/2006 Gr. Beta 4.12 +/- 0.14 3.82 +/- 0.13 3.97 +/- 0.10 Fail F-3311, 3312 2/9/2006 K-40 2.68 +/- 0.37 2.76 +/- 0.39 2.72 +/- 0.27 Pass SW-780, 781 2/14/2006 Gr. Alpha 4.09 +/- 1.52 3.22 +/- 1.37 3.66 +/- 1.03 Pass SW-780, 781 2/14/2006 Gr. Beta 5.91 +/- 0.90 5.89 +/- 0.92 5.90 +/- 0.64 Pass DW-934, 935 2/17/2006- 1-131 0.35 +/- 0.22 0.31 +/- 0.25 0.33 +/- 0.16 Pass DW-1024, 1025 2/24/2006 1-131 0.24 +/- 0.26 0.53 +/- 0.24 0.39 +/- 0.18 Pass MI-1078, 1079 3/1/2006 Sr-90 1.42 +/- 0.39 1.30 +/- 0.62 1.36 +/- 0.37 Pass F-1357, 1358 3/10/2006 Gr. Beta 3.77 +/- 0.07 3.71 +/- 0.07 3.74 +/- 0.05 Pass F-1357, 1358 3/10/2006 K-40 2.46 +/- 0.32 2.32 +/- 0.44 2.39 +/- 0.27 Pass MI-1469, 1470 3/14/2006 K-40 1396.30 +/- 120.80 1335.60 +/- 113.80 1365.95 +/- 82.98 Pass CF-1538, 1539 3/21/2006 K-40 13.66 +/- 0.81 13.97 +/- 0.68 13.81 +/- 0.53 Pass WW-1583, 1584 3/22/2006 Gr. Beta 7.66 +/- 0.73 8.87 +/- 0.75 8.26 +/- 0.52 Pass DW-1 955, 1956 3/27/2006 Gr. Beta 2.25 +/- 0.60 3.15 +/- 0.59 2.70 +/- 0.42 Pass MI-1760, 1761 3/29/2006 K-40 1271.00 +/- 89.00 1378.00 +/- 113.00 1324.50 +/- 71.92 Pass AP-2603, 2604 3/29/2006 Be-7 0.067 +/- 0.015 0.056 +/- 0.010 0.062 +/- 0.009 Pass E-1997, 1998 4/3/2006 Gr. Beta 1.82 +/- 0.07 1.87 +/- 0.07 1.85 +/- 0.05 Pass E-1997, 1998 4/3/2006 K-40 1.28 +/- 0.15 1.24 +/- 0.21 1.26 +/-0.13 Pass AP-2818, 2819 4/3/2006 Be-7 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 Pass SWU-2863, 2864 4/3/2006 Gr. Beta 3.20 +/- 1.26 4.77 +/- 1.30 3.99 +/- 0.91 Pass SS-2389, 2390 4/11/2006 Gr. Beta 10.53 +/- 0.96 9.38 +/- 0.84 9.96 +/- 0.64 Pass SS-2389, 2390 4/11/2006 K-40 5.51 +/- 0.42 5.79 +/- 0.40 5.65 +/- 0.29 Pass DW-2773, 2774 4/21/2006 1-131 0.74 +/- 0.23 0.53 +/- 0.40 0.63 +/- 0.23 Pass SL-2932, 2933 5/1/2006 Be-7 1.28 +/- 0.19 1.27 +/- 0.17 1.28 +/- 0.13 Pass SL-2932, 2933 5/1/2006 Gr. Beta 6.09 +/- 0.33 5.65 +/- 0.31 5.87 +/- 0.23 Pass SL-2932, 2933 5/1/2006 K-40 3.13 +/- 0.41 3.09 +/- 0.36 3.11 +/- 0.27 Pass BS-3103, 3104 5/1/2006 Gr. Beta 8.27 +/- 1.46 9.03 +/- 1.59 8.65 +/- 1.08 Pass BS-3103, 3104 5/1/2006 K-40 6288.20 +/- 585.20 5643.70 +/- 599.80 5965.95 +/- 418.99 Pass MI-3037, 3038 5/2/2006 K-40 1238.90 +/- 98.59 1301.00 +/- 103.90 1269.95 +/- 71.62 Pass MI-3037, 3038 5/2/2006 Sr-90 1.76 +/- 0.42 1.48 +/- 0.42 1.62 +/- 0.29 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-3124, 3125 5/9/2006 K-40 1032.30 +/- 91.12 1103.60 +/- 120.50 1067.95 +/- 75.54 Pass SW-3145, 3146 5/9/2006 Gr. Alpha 4.85 +/- 1.68 4.12 +/- 1.62 4.48 +/- 1.17 Pass SW-3145, 3146 5/9/2006 Gr. Beta 8.94 +/- 1.46 9.14 +/- 1.36 9.04 +/- 1.00 Pass MI-3236, 3237 5/10/2006 K-40 1412.40 +/- 119.10 1427.90 +/- 127.70 1420.15 +/- 87.31 Pass F-3422, 3423 5/19/2006 H-3 8175.00 +/- 252.00 8268.00 +/- 253.00 8221.50 +/- 178.54 Pass G-3491, 3492 5/24/2006 Gr. Beta 8.89 +/- 0.18 9.03 +/- 0.19 8.96 +/- 0.13 Pass G-3491, 3492 5/24/2006 K-40 5.60 +/- 0.71 6.30 +/- 0.78 5.95 +/- 0.53 Pass SO-3539, 3540 5/24/2006 Gr. Beta 19.57 +/- 1.99 18.98 +/- 1.91 19.27 +/- 1.38 Pass SO-3539, 3540 5/24/2006 K-40 12.55 +/- 0.89 11.49 +/- 0.59 12.02 +/- 0.53 Pass WW-3751, 3752 5/25/2006 Gr. Beta 9.85 +/- 0.79 8.96 +/- 0.74 9.41 +/- 0.54 Pass F-3617, 3618 5/30/2006 K-40 2.42 +/- 0.38 2.53 +/- 0.37 2.47 +/- 0.27 Pass SL-3641, 3642 6/1/2006 Be-7 1.41 +/- 0.19 1.31 +/- 0.27 1.36 +/- 0.17 Pass SL-3641, 3642 6/1/2006 Gr. Beta 5.03 +/- 0.18 5.30 +/- 0.19 5.17 +/- 0.13 Pass SL-3641, 3642 6/1/2006 K-40 2.21 +/- 0.26 2.14 +/- 0.37 2.18 +/- 0.23 Pass MI-3886, 3887 6/12/2006 K-40 1424.20 +/- 118.20 1318.80 +/- 110.50 1371.50 +/- 80.90 Pass VE-3949, 3950 6/13/2006 Gr. Alpha 0.13 +/- 0.06 0.16 +/- 0.07 0.15 +/- 0.05 Pass VE-3949, 3950 6/13/2006 Gr. Beta 4.53 +/- 0.19 4.47 +/- 0.18 4.50 +/- 0.13 Pass VE-3949, 3950 6/13/2006 K-40 6.02 +/- 0.66 5.33 +/- 0.66 5.67 +/- 0.47 Pass BS-4016, 4017 6/13/2006 Co-60 0.18 +/- 0.03 0.15 +/- 0.03 0.16 +/- 0.02 Pass BS-4016, 4017 6/13/2006 Cs-1 37 1.97 +/- 0.09 2.01 +/- 0.09 1.99 +/- 0.06 Pass BS-4016, 4017 6/13/2006 K-40 11.03 +/- 0.76 10.45 +/- 0.78 10.74 +/- 0.54 Pass MI-3992, 3993 6/14/2006 K-40 1358.50 +/- 166.40 1395.80 +/- 122.70 1377.15 +/- 103.37 Pass LW-4175, 4176 6/16/2006 H-3 482.11 +/- 90.25 397.50 +/- 86.88 439.81 +/- 62.63 Pass W-4130, 4131 6/21/2006 H-3 401.50 +/- 87.85 236.28 +/- 80.89 318.89 +/- 59.71 Pass AV-4330, 4331 6/26/2006 K-40 1717.10 +/- 244.30 1893.10 +/- 223.30 1805.10 +/- 165.49 Pass SWU-4489, 4490 6/27/2006 Gr. Beta 1.70 +/- 0.38 1.93 +/- 0.38 1.82 +/- 0.27 Pass AP-4909, 4910 6/29/2006 Be-7 0.11 +/- 0.01 0.11 +/- 0.02 0.11 +/- 0.01 Pass AP-4952, 4953 6/29/2006 Be-7 0.08 +/- 0.02 0.10 +/- 0.02 0.09 +/- 0.01 Pass AP-4930, 4931 7/3/2006 Be-7 0.08 +/- 0.02 0.07 +/- 0.01 0.08 +/- 0.01 Pass E-4399, 4400 7/5/2006 Gr. Beta 1.85 +/- 0.05 1.85 +/- 0.05 1.85 +/- 0.04 Pass E-4399, 4400 7/5/2006 K-40 1.25 +/- 0.19 1.24 +/- 0.18 1.25 +/- 0.13 Pass G-4420, 4421 7/5/2006 Be-7 0.82 +/- 0.20 0.61 +/- 0.14 0.72 +/- 0.12 Pass G-4420, 4421 7/5/2006 Gr. Beta 13.20 +/- 0.40 14.00 +/- 0.40 13.60 +/- 0.28 Pass G-4420, 4421 7/5/2006 K-40 9.96 +/- 0.44 10.06 +/- 0.82 10.01 +/- 0.47 Pass DW-60432, 60433 7/6/2006 Gr. Alpha 3.24 +/- 1.35 2.49 +/- 1.33 2.87 +/- 0.95 Pass DW-60514, 60515 7/10/2006 Gr. Alpha 3.70 +/- 1.12 3.09 +/- 1.16 3.40 +/- 0.81 Pass DW-60449, 60450 7/11/2006 Gr. Alpha 6.87 +/- 1.26 4.77 +/- 1.09 5.82 +/- 0.83 Pass MI-4599, 4600 7/12/2006 K-40 1403.50 +/- 118.80 1330.40 +/- 116.50 1366.95 +/- 83.20 Pass MI-4599, 4600 7/12/2006 Sr-90 0.59 +/- 0.34 0.70 +/- 0.35 0.65 +/- 0.24 Pass MI-4667, 4668 7/12/2006 K-40 1286.60 +/- 92.62 1358.60 +/- 158.40 1322.60 +/- 91.75 Pass LW-4823, 4824 7/14/2006 Gr. Beta 1.75 +/- 0.60 2.51 +/- 0.59 2.13 +/- 0.42 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance DW-60502, 60503 7/19/2006 Gr. Alpha 16.27 +/- 2.49 21.41 +/- 3.21 18.84 +/- 2.03 Pass DW-60526, 60527 7/21/2006 Gr. Alpha 14.06 +/- 1.82 15.57 +/- 1.77 14.82 +/- 1.27 Pass DW-60539, 60540 7/21/2006 Gr. Alpha 5.09 +/- 0.95 6.23 +/- 1.05 5.66 +/- 0.71 Pass MI-5125, 5126 7/25/2006 K-40 1480.60 +/- 118.30 1402.60 +/- 120.80 1441.60 +/- 84.54 Pass DW-60609, 60610 7/26/2006 Gr. Alpha 1.00 +/- 1.10 2.70 +/- 1.30 1.85 +/- 0.85 Pass DW-60621, 60622 7/31/2006 Gr. Alpha 3.70 +/- 1.00 1.90 +/- 0.80 2.80 +/- 0.64 Pass SL-5265, 5266 8/1/2006 Be-7 1.10 +/- 0.46 1.38 +/- 0.52 1.24 +/- 0.35 Pass SL-5265, 5266 8/1/2006 Sr-90 0.10 +/- 0.03 0.16 +/- 0.03 0.13 +/- 0.02 Pass SL-5265, 5266 8/1/2006 Gr. Beta 4.41 +/- 0.41 3.46 +/- 0.57 3.94 +/- 0.35 Pass SL-5265, 5266 8/1/2006 K-40 1.19 +/- 0.52 0.87 +/- 0.52 1.03 +/- 0.37 Pass VE-5286, 5287 8/1/2006 Be-7 1.21 +/- 0.30 1.32 +/- 0.20 1.27 +/- 0.18 Pass VE-5286, 5287 8/1/2006 Gr. Beta 9.67 +/- 0.35 9.37 +/- 0.35 9.52 +/- 0.25 Pass VE-5286, 5287 8/1/2006 K-40 6.25 +/- 0.81 6.50 +/- 0.48 6.38 +/- 0.47 Pass SW-5383, 5384 8/8/2006 Gr. Alpha 3.24 +/- 1.35 2.94 +/- 1.35 3.09 +/- 0.96 Pass SW-5383, 5384 8/8/2006 Gr. Beta 4.86 +/- 0.86 5.46 +/- 0.87 5.16 +/- 0.61 Pass SW-5971, 5972 8/8/2006 H-3 119.90 +/- 78.14 144.41 +/- 79.23 132.15 +/- 55.64 Pass VE-5404, 5405 8/10/2006 Be-7 0.77 +/- 0.24 1.01 +/- 0.26 0.89 +/- 0.18 Pass VE-5404, 5405 8/10/2006 K-40 4.71 +/- 0.63 4.01 +/- 0.58 4.36 +/- 0.43 Pass DW-5480, 5481 8/11/2006 H-3 169.08 +/- 85.52 133.65 +/- 83,96 151.36 +/- 59.92 Pass DW-60645, 60646 8/15/2006 Gr. Alpha 10.41 +/- 1.78 10.97 +/- 1.85 10.69 +/- 1.28 Pass W-5602, 5603 8/16/2006 H-3 2118.79 +/- 151.55 2181.82 +/- 153.09 2150.30 +/- 107.71 Pass DW-60634, 60635 8/18/2006 Gr. Alpha 12.99 +/- 1.84 9.67 +/- 1.61 11.33 +/- 1.22 Pass DW-60634, 60635 8/18/2006 Gr. Beta 10.51 +/- 1.33 8.61 +/- 1.18 9.56 +/- 0.89 Pass MI-5793, 5794 8/22/2006 K-40 1264.00 +/- 115.00 1377.00 +/- 121.00 1320.50 +/- 83.47 Pass SWU-6150, 6151 8/29/2006 Gr. Beta 1.84 +/- 0.28 1.81 +/- 0.28 1.82 +/- 0.20 Pass DW-60657, 60658 8/29/2006 Gr. Alpha 2.33 +/- 0.80 2.90 +/- 0.78 2.62 +/- 0.56 Pass CF-7450, 7451 9/5/2006 Be-7 0.78 +/- 0.45 0.78 +/- 0.27 0.78 +/- 0.26 Pass SL-6085, 6086 9/5/2006 Co-60 0.22 + 0.03 0.21 +/- 0.02 0.22 +/- 0.02 Pass SL-6085, 6086 9/5/2006 Gr. Beta 5.47 + 069 4.63 +/- 0.58 5.05 +/- 0.45 Pass SL-6085, 6086 9/5/2006 K-40 1.91 + 0.28 2.06 +/- 0.41 1.99 +/- 0.25 Pass DW-60695, 60696 9/11/2006 Gr. Alpha 3.93 + 1.17 4.62 +/- 1.12 4.28 +/- 0.81 Pass LW-6266, 6267 9/13/2006 Gr. Beta 3.09 + 0.48 2.98 +/- 0.48 3.03 +/- 0.34 Pass MI-6424, 6425 9/19/2006 Sr-90 0.78 + 0.38 1.11 +/- 0.37 0.95 +/- 0.27 Pass DW-60715, 60716 9/19/2006 Gr. Alpha 1.30 + 1.00 2.23 +/- 1.01 1.77 +/- 0.71 Pass SO-6597, 6598 9/22/2006 Cs-137 0.18 +/- 0.04 0.18 +/- 0.04 0.18 +/- 0.03 Pass SO-6597, 6598 9/22/2006 K-40 10.25 +/- 0.66 10.11 +/- 0.64 10.18 +/- 0.46 Pass SWU-6718, 6719 9/26/2006 Gr. Beta 3.45 +/- 1.21 2.78 +/- 1.19 3.12 +/- 0.85 Pass SO-6668, 6669 9/27/2006 Cs-1 37 0.13 +/- 0.04 0.13 +/- 0.02 0.13 +/- 0.02 Pass SO-6668, 6669 9/27/2006 K-40 13.04 +/- 0.90 12.41 +/- 0.54 12.72 +/- 0.53 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)9 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-6760, 6761 10/2/2006 K-40 1413.10 +/- 113.20 1187.30 +/- 155.20 1300.20 +/- 96.05 Pass G-6797, 6798 10/2/2006 Be-7 4.70 +/- 0.31 4.56 +/- 0.41 4.63 +/- 0.26 Pass G-6797, 6798 10/2/2006 Gr. Beta 6.89 +/- 0.26 7.04 +/- 0.24 6.97 +/- 0.18 Pass G-6797, 6798 b 10/2/2006 K-40 5.39 +/- 0.35 4.36 +/- 0.47 4.88 +/- 0.29 Fail AP-7531, 7532 10/3/2006 Be-7 0.07 +/- 0.01 0.08 +/-0.01 0.08 +/- 0.01 Pass AP-7552, 7553 10/3/2006 Be-7 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-7573, 7574 10/3/2006 Be-7 0.08 +/- 0.02 0.08 +/- 0.01 0.08 +/- 0.01 Pass SO-7103, 7104 10/4/2006 Cs-137 0.25 +/- 0.05 0.27 +/- 0.06 0.26 +/- 0.04 Pass SO-7103, 7104 10/4/2006 K-40 12.95 +/- 1.12 12.22 +/- 1.07 12.58 +/- 0.77 Pass DW-60759, 60760 10/5/2006 Gr. Alpha 4.93 +/- 0.97 5.04 +/- 1.03 4.99 +/- 0.71 Pass MI-7037, 7038 10/10/2006 K-40 1326.10 +/- 115.20 1251.40 +/- 115.70 1288.75 +/- 81.64 Pass VE-7058, 7059 10/10/2006 Gr. Alpha 0.18 +/- 0.11 0.32 +/- 0.14 0.25 +/- 0.09 Pass VE-7058, 7059 10/10/2006 Gr. Beta 9.21 +/- 0.34 8.83 +/- 0.36 9.02 +/- 0.25 Pass VE-7058, 7059 10/10/2006 K-40 10.90 +/- 0.65 10.42 +/- 0.80 10.66 +/- 0.52 Pass SS-7079, 7080 10/10/2006 Cs-1 37 0.04 +/- 0.01 0.04 +/- 0.02 0.04 +/- 0.01 Pass SS-7079, 7080 10/10/2006 Gr. Beta 12.23 +/- 2.46 11.76 +/- 2.23 11.99 +/- 1.66 Pass SS-7079, 7080 10/10/2006 K-40 7.23 +/- 0.36 7.37 +/- 0.40 7.30 +/- 0.27 Pass MI-7208, 7209 10/11/2006 K-40 1295.20 +/- 116.90 1386.90 +/- 119.10 1341.05 +/- 83.44 Pass CF-7450, 7451 10/18/2006 K-40 20.40 +/- 0.84 19.54 +/- 0.99 19.97 +/- 0.65 Pass LW-7945, 7946 10/26/2006 Gr. Beta 1.30 +/- 0.37 1.44 +/- 0.36 1.37 +/- 0.26 Pass F-7971, 7972 10/29/2006 K-40 3.63 +/- 0.54 3.33 +/- 0.43 3.48 +/- 0.34 Pass SWU-8194, 8195 10/31/2006 Gr. Beta 1.84 +/- 0.28 1.43 +/- 0.28 1.64 +/- 0.20 Pass BS-8017, 8018 11/1/2006 Gr. Beta 10.54 +/- 1.72 10.17 +/- 1.73 10.36 +/- 1.22 Pass BS-8017, 8018 11/1/2006 K-40 10.00 +/- 0.53 9.60 +/- 0.69 9.80 +/- 0.44 Pass LW-8215, 8216 11/1/2006 Gr. Beta 2.23 +/- 0.61 1.64 +/- 0.37 1.93 +/- 0.35 Pass F-8345, 8346 11/2/2006 K-40 2.84 +/- 0.42 2.89 +/- 0.40 2.86 +/- 0.29 Pass BS-8366, 8367 11/2/2006 K-40 13.69 +/- 0.66 13.61 +/- 0.78 13.65 +/- 0.51 Pass MI-8083, 8084 11/6/2006 K-40 1295.00 +/- 121.20 1374.80 +/- 162.80 1334.90 +/- 101.48 Pass WW-8259, 8260 11/7/2006 H-3 337.00 +/- 95.00 295.00 +/- 93.00 316.00 +/- 66.47 Pass MI-8484, 8485 11/22/2006 K-40 1405.80 +/- 87.06 1390.70 +/- 103.60 1398.25 +/- 67.66 Pass SO-8619, 8620 11/27/2006 Cs-137 0.74 +/- 0.08 0.69 +/- 0.06 0.71 +/- 0.05 Pass SO-8619, 8620 11/27/2006 Gr. Alpha 16.54 +/- 5.65 12.24 +/- 4.90 14.39 +/- 3.74 Pass SO-8619, 8620 11/27/2006 Gr. Beta 24.99 +/- 3.88 28.66 +/- 3.95 26.82 +/- 2.77 Pass SO-8619, 8620 11/27/2006 K-40 12.21 +/- 1.11 12.92 +/- 0.83 12.57 +/- 0.69 Pass SWT-8641, 8642 11/29/2006 Gr. Beta 2.83 +/- 0.47 2.89 +/- 0.45 2.86 +/- 0.33 Pass SWT-9436, 9437 12/26/2006 Gr. Beta 2.39 +/- 0.64 2.25 +/- 0.60 2.32 +/- 0.44 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

b 200 minute count time or longer, resulting in lower error.

A5-4

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1082 01/01/06 Am-241 0.16 +/- 0.06 0.16 0.11 -0.20 Pass STVE-1082 01/01/06 Co-57 10.40 +/- 0.20 8.58 6.00 -11.15 Pass STVE-1082 01/01/06 Co-60 5.00 +/- 0.20 4.52 3.16 -5.88 Pass STVE-1082 e 01/01/06 Cs-1 34 < 0.20 0.00 Pass STVE-1082 01/01/06 Cs-1 37 3.40 +/- 0.20 3.07 2.15 -4.00 Pass STVE-1082 01/01/06 Mn-54 6.90 +/- 0.20 6.25 4.37 -8.12 Pass STVE- 10 8 2 f 01/01/06 Pu-238 0.08 +/- 0.03 0.14 0.10 -0.18 Fail STVE-1082 01/01/06 Pu-239/40 0.17 +/- 0.03 0.16 0.11 -0.21 Pass STVE-1 082 01/01/06 Sr-90 1.40 +/- 0.20 1.56 1.09 - 2.03 Pass STVE-1 082 01/01/06 U-233/4 0.24 +/- 0.05 0.21 0.15 -0.27 Pass STVE-1 082 01/01/06 U-238 0.19 +/- 0.04 0.22 0.15 - 0.28 Pass STVE-1082 01/01/06 Zn-65 11.10 +/- 0.50 9.80 6.86 - 12.74 Pass STSO-1083 01/01/06 Am-241 54.60 +/- 5.50 57.08 39.96 - 74.20 Pass STSO-1083 01/01/06 Co-57 762.90 +/- 12.70 656.29 459.40 -853.18 Pass STSO-1 083 01/01/06 Co-60 504.90 +/- 3.10 447.10 312.97 -581.23 Pass STSO-1 083 e 01/01/06 Cs-1 34 < 1.70 0.00 Pass STSO-1083 01/01/06 Cs-137 406.50 +/- 3.70 339.69 237.78 -441.60 Pass STSO-1 083 01/01/06 K-40 719.20 +/- 18.40 604.00 422.80 - 785.20 Pass STSO-1083 01/01/06 Mn-54 415.60 +/- 4.80 346.77 242.74 - 450.80 Pass STSO-1 083 01/01/06 Ni-63 261.40 +/- 14.70 323.51 226.46 -420.56 Pass STSO-1083' 01/01/06 Pu-238 14.60 +/- 2.90 61.15 42.81 - 79.50 Fail STSO-1 083 01/01/06 Pu-239/40 14.60 +/- 2.40 45.85 32.09 - 59.61 Fail STSO-1083 01/01/06 U-233/4 13.50 +/- 1.70 37.00 25.90 -48.10 Fail STSO-1 083 01/01/06 U-238 15.40 +/- 1.80 38.85 27.20 - 50.50 Fail STSO-1083 01/01/06 Zn-65 783.40 +/- 7.00 657.36 460.15 -854.57 Pass STAP-1 084 01/01/06 Gr. Alpha 0.26 +/- 0.02 0.36 0.00 - 0.72 Pass STAP-1084 01/01/06 Gr. Beta 0.51 +/- 0.03 0.48 0.24 - 0.72 Pass STAP-1 085 01/01/06 Am-241 0.12 +/- 0.02 0.09 0.07 -0.12 -Pass STAP-1 085 01/01/06 Co-57 4.32 +/- 0.10 4.10 2.87 - 5.32 Pass STAP-1 085 01/01/06 Co-60 2.24 +/- 0.16 2.19 1.53 -2.84 Pass STAP-1 085 01/01/06 Cs-1 34 2.96 +/- 0.19 2.93 2.05 - 3.81 Pass STAP-1085 01/01/06 Cs-137 2.64 +/- 0.20 2.53 1.77 -3.29 Pass STAP-1 085' 01/01/06 Pu-238 0.03 +/- 0.01 0.07 0.05 - 0.09 Fail STAP-1085 e 01/01/06 Pu-239/40 < 0.01 0.00 Pass STAP-1 085 01/01/06 Sr-90 0.77 +/- 0.21 0.79 0.55 - 1.03 Pass STAP-1 085 01/01/06 U-233/4 0.03 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1 085 01/01/06 U-238 0.02 +/- 0.01 0.02 0.01 - 0.03 Pass STAP-1 085 01/01/06 Zn-65 3.94 +/- 0.44 3.42 2.40 - 4.45 Pass A6-1

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1 086 01/01/06 Am-241 1.29 +/- 0.05 1.30 0.91 -1.69 Pass STW-1 086 01/01/06 Co-57 177.10 +/- 1.00 166.12 116.28 -215.96 Pass STW-1086 01/01/06 Co-60 158.30 +/- 1.00 153.50 107.45 - 199.55 Pass STW-1 086 01/01/06 Cs-1 34 96.40 +/- 1.50 95.10 66.57 - 123.63 Pass STW-1 086 e 01/01/06 Cs-1 37 < 0.80 0.00 Pass STW-1086 01/01/06 Fe-55 102.50 +/- 18.10 129.60 90.72 - 168.48 Pass STW-1086 01/01/06 H-3 956.60 +/- 16.50 952.01 666.41 - 1238.00 Pass STW-1086 01/01/06 Mn-54 335.30 +/- 2.20 315.00 220.50 - 409.50 Pass STW-1086 01/01/06 Ni-63 62.90 +/- 3.60 60.34 42.24 - 78.44 Pass STW-1 086 01/01/06 Pu-238 0.96 +/- 0.07 0.91 0.70 -1.30 Pass STW-1086 e 01/01/06 Pu-239/40 < 0.20 0.00 Pass STW-1086 01/01/06 Sr-90 12.80 +/- 1.60 13.16 9.21 -17.11 Pass STW-1086 01/01/06 Tc-99 22.30 +/- 1.20 23.38 16.37 - 30.39 Pass STW-1086 01/01/06 U-233/4 2.02 +/- 0.12 2.09 1.46 - 2.72 Pass STW-1086 01/01/06 U-238 2.03 +/- 0.12 2.17 1.52 - 2.82 Pass STW-1086 01/01/06 Zn-65 249.50 +/- 3.40 228.16 159.71 - 296.61 Pass STW-1 087 01/01/06 Gr. Alpha 0.59 +/- 0.10 0.58 0.00 -1.16 Pass STW-1 087 01/01/06 Gr. Beta 1.69 +/- 0.07 1.13 0.56 -1.70 Pass STVE-1 098 e 07/01/06 Co-57 <0.14 .0.00 Pass STVE-1098g 07/01/06 Co-60 6.89 +/- 0.17 5.81 4.06 - 7.55 Pass 8TVE-1098 07/01/06 Cs-1 34 8.46 +/- 0.16 7.49 5.24 - 9.73 Pass STVE-1 098 07/01/06 Cs-1 37 6.87 +/- 0.29 5.50 3.85 -7.14 Pass STVE-1098 07/01/06 Mn-54 10.36 +/- 0.29 8.35 5.85 - 10.86 Pass STVE-1098 07/01/06 Zn-65 7.46 +/- 0.50 5.98 4.19 - 7.78 Pass STSO-1099 07/01/06 Am-241 130.00 +/- 11.60 105.47 73.83 -137.11 Pass STSO-1099 07/01/06 Co-57 784.90 +/- 3.80 676.33 473.43 - 879.23 Pass STSO-1 099 07/01/06 Co-60 2.10 +/- 0.90 1.98 0.00 - 5.00 Pass STSO-1 099 07/01/06 Cs-1 34 .500.70 +/- 7.40 452.13 316.49 - 587.77 Pass STSO-1099 07/01/06 Cs-1 37 624.20 +/- 4.90 525.73 368.01 - 683.45 Pass STSO-1 099 07/01/06 K-40 701.30 +/- 3.40 604.00 423.00 - 785.00 Pass STSO-1099 07/01/06 Mn-54 699.20 +/- 5.20 594.25 415.98 - 772.52 Pass STSO-1 099 07/01/06 Ni-63 614.40 +/- 17.10 672.30 470.60 -874.00 Pass STSO-1 099 07/01/06 Pu-238 79.90 +/- 5.80 82.00 57.00 - 107.00 Pass STSO-1 099 e 07/01/06 Pu-239/40 < 0.70 0.00 Pass STSO-1099 07/01/06 U-233/4 150.50 +/- 5.90 152.44 106.71 -198.17 Pass STSO-1099 07/01/06 U-238 151.60 +/- 6.00 158.73 111.11 - 206.35 Pass STSO-1099 07/01/06 Zn-65 1021.90 +/-+9.20 903.61 632.53 - 1175.00 Pass STAP-1100 07/01/06 Am-241 0.16 +/- 0.03 0.14 0.10 -0.19 Pass STAP-1 100 07/01/06 Co-57 2.17 +/- 0.06 2.58 1.81 - 3.36 Pass STAP-1100 07/01/06 Co-60 1.38 +/- 0.07 1.58 1.10 - 2.05 Pass STAP-1 100 07/01/06 Cs-134 2.52 +/- 0.13 3.15 2.20 - 4.09 Pass A6-2

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STAP-1100 07/01/06 Cs-1 37 1.64 +/- 0.08 1.81 1.26 - 2.35 Pass STAP-1 100 07/01/06 Mn-54 1.76 +/- 0.18 1.92 1.34 - 2.50 Pass STAP-1 100 07/01/06 Pu-238 0.09 +/- 0.02 0.12 0.08 -0.15 Pass STAP- 1100 07/01/06 Sr-90 0.66 +/- 0.21 0.62 0.43 - 0.81 Pass STAP-1100 07/01/06 U-233/4 0.15 +/- 0.02 0.13 0.09 -0.17 Pass STAP-1 100 07/01/06 U-238 0.13 +/- 0.02 0.14 0.10 -0.18 Pass STAP-1100 e 07/01/06 Zn-65 < 0.07 0.00 Pass STAP-1101 07/01/06 Gr. Alpha 0.08 +/- 0.03 0.29 0.00 - 0.58 Pass STAP-1 101 07/01/06 Gr. Beta 0.41 +/- 0.05 0.36 0.18 -0.54 Pass STW-1 102 07/01/06 Gr. Alpha 0.76 +/- 0.07 1.03 0.00 -2.07 Pass STW-1 102 07/01/06 Gr. Beta 1.23 +/- 0.06 1.03 0.52 -1.54 Pass STW-1103 07/01/06 Am-241 1.86 +/- 0.09 2.31 1.62 -3.00 Pass STW-1 103 07/01/06 Co-57 224.10 +/- 1.20 213.08 149.16 -277.00 Pass STW-1 103 07/01/06 Co-60 49.40 +/- 0.50 47.50 33.20 -61.80 Pass STW-1103 07/01/06 Cs-1 34 112.70 +/- 0.90 112.82 78.97 -146.66 Pass STW-1 103 07/01/06 Cs-1 37 206.60 +/- 1.40 196.14 137.30 -254.98 Pass STW-1103 07/01/06 Fe-55 138.40 +/- 5.40 165.40 115.80 -215.00 Pass STW-1 103 07/01/06 H-3 446.50 +/- 11.80 428.85 300.20 -557.50 Pass STW-1103 e 07/01/06 Mn-54 < 0.30 0.00 Pass STW-1 103 07/01/06 Ni-63 116.70 +/- 3.60 118.62 83.03 -154.21 Pass STW-1 103 07/01/06 Pu-238 1.27 +/- 0.07 1.39 0.97 -1.81 Pass STW-1 103 07/01/06 Pu-239/40 1.67 +/- 0.08 1.94 1.36 -2.52 Pass STW-1 103 07/01/06 Sr-90 16.40 +/- 1.90 15.69 10.98 -20.40 Pass STW-1103 07/01/06 Tc-99 29.40 +/- 1.10 27.15 19.00 -35.29 Pass STW-1 103 07/01/06 U-233/4 1.97 +/- 0.08 2.15 1.50 -2.80 Pass STW-1 103 07/01/06 U-238 1.97 +/- 0.08 2.22 1.55 -2.89 Pass STW-1103 07/01/06 Zn-65 192.50 +/- 2.40 176.37 123.46 - 229.28 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b

Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.

e Included in the MAPEP as a false positive.

f Difficulties with the'analyses for transuranics isotopes in solid samples (Filters, Soil and vegetation),

were attributed to incomplete dissolution of the samples. Soil samples were repeated, results of reanalyses:

Pu-238, 53.1 + 5.3 bq/kg. Pu-239/240, 42.4 +/- 4.7 bq/kg. U-233/4, 33.3 +/- 3.5 bq/kg. U-238, 35.5 +/- 3.6 bq/kg.

g The July vegetation sample was provided in two separate geometries, (100 ml. and 500 ml.). Results reported here used the 500 ml. standard size geometry. Results for the 100 ml. geometry showed approximately a 15% higher bias.

A6-3

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reportingq Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows: x _s where: x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66a uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x 1 + s1 and x2 +/- s2 Reported result: x +/- s; where x = (1/2) (x1 +x 2)ands= (1/2) sI +$2 3.2. Individual results: < L1 , < L2 Reported result: < L, where L = lower of Li and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x > L; <L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1 , x 2 . . . Xn are defined as follows:

- 1 x- x)2 x =n Ix n-1 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained number s are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.

B-2

APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1

Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas Air (pCi/m3) Water (pCi/L)

-3 Gross alpha 1 x10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b

Iodine-1 31 2.8 x 10-1 Cesium-1 37 1,000 Barium-1 40 8,000 Iodine-1 31 1,000 Potassium-40 4,000 Gross alpha 2 Gross beta 10 6

Tritium 1 x 10 a

Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

Concentrations may be averaged over a period not greater than one year.

Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.

C A natural radionuclide.

C-2

APPENDIX D Sampling Location Maps D-1

0000 Figure D-1, Sample Collection and Analysis program: TLD locations, Inner ring (Table 5.2).

D-2

ME rM-I -2.5 1=1 CL 0I o ww Figure 0-2. Sample Collection and Analysis program:TLD locations, Outer ring (Table 5.2).

D-3

qJ18M.

a" CDI zL CO ,¥ Figure D-3. Sample Collection and Analysis program: TOD locations, Controls (Table 5.2).

D-4

0 R

-SUL CO Lr)

(L CL

0) J3 Do Cn Cn C%

Figure D-4. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Milk sampling locations. (Table 5.2)

D-5

Ii ago Figure D-5. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground Water and Shoreline sampling locations (Table 5-2.)

D-6